|
|---|
Category:ARCHIVE RECORDS
MONTHYEARML20154H9871998-08-28028 August 1998
Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release
ML20154P8941998-05-13013 May 1998
Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas
ML20217E1661998-03-18018 March 1998
Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust
ML20217E1971998-03-17017 March 1998
Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening
ML20217E1171998-03-17017 March 1998
Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability
ML20217F9501997-07-24024 July 1997
Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers
ML20133F6511997-01-14014 January 1997
Press Release 97-03, NRC Receives Application from DOE for License to Store TMI Fuel Debris at Inel
ML20134M2121996-11-22022 November 1996
Press Release 96-165, NRC Begins First of Series of Design Insps at Nuclear Power Plants
ML20148T7361996-11-0808 November 1996
Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals
ML20148T7511996-11-0606 November 1996
Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level
ML20134D5471996-10-28028 October 1996
Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened
ML20128Q3321996-10-18018 October 1996
Press Release 96-146, NRC Establishes Special Projects Ofc to Oversee Insp & Licensing Activities at Millstone & Haddam Neck Plants
ML20129E9941996-10-10010 October 1996
Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity
ML20148T6971996-09-11011 September 1996
Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs
ML20148T6801996-09-0606 September 1996
Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level
ML20148F0251994-02-0808 February 1994
Rev 0 to Condensate Storage Tank B
ML20148F0081994-02-0808 February 1994
Rev 0 to Condensate Storage Tank a
ML20148F0321993-12-0808 December 1993
Rev 0 to Bwst
ML20148F1331993-09-30030 September 1993
Rev 0 to Make-Up Tank
ML20148F1601993-09-27027 September 1993
Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways
ML20058P1681993-09-27027 September 1993
Package Consisting of Attachment to Employee Concerns Programs
ML20148F0541993-09-17017 September 1993
Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A
ML20057B9641993-09-10010 September 1993
AX114 & AX115 Ci Loading
ML20057C0201993-09-0101 September 1993
Notation Vote Approving w/comment,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20148F1451993-09-0101 September 1993
Rev 0 to Nuc Serv Closed Cooling Water Surge Tank
ML20057C0191993-08-31031 August 1993
Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20148F1071993-08-31031 August 1993
Rev 0 to Intermediate Colsed Cooling Surge Tank
ML20148F1221993-08-31031 August 1993
Rev 0 to Intermediate Closed Cooling Chem Mix Tank
ML20148F1521993-08-31031 August 1993
Rev 0 to Nuc Svc Cool Chem Mix Tank
ML20057C0211993-08-30030 August 1993
Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20057B9581993-08-27027 August 1993
FH109/FH300 Ci Estimate
ML20057C0161993-08-26026 August 1993
Notation Vote approving,SECY-93-238, Three Mile Island Nuclear Station Unit 2 Possession Only License Amend
ML20126M2391992-07-13013 July 1992
Package of Documents,Including Index of Briefing Papers & Actual Papers Re License Renewal,Design Certification Process,Below Regulatory Concern & Resident Inspector Program
ML20196K6431991-07-20020 July 1991
Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis
ML20151M9601987-07-20020 July 1987
Package of NRC Administered Requalification Exam Results Summary
IA-86-608, Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island1987-01-29029 January 1987
Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island
ML20213A0411987-01-29029 January 1987
Undated Statement Entitled, Status of Radiological Impact from Accident at Three Mile Island
IA-86-293, Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response1986-10-0909 October 1986
Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response
ML20215L2161986-10-0909 October 1986
Package of Performance Appraisal Observations,Including Observation of TMI Shift Simulator Use & ATWS Response
ML20154M5021985-05-23023 May 1985
Notation Vote Response Sheet Approving SECY-85-153,providing Info to Advisory Panel on TMI-2 Cleanup
ML20129F4831985-05-0909 May 1985
Package of Compilations of Results of Operator Licensing & Requalification Exams
ML20126B8311984-12-11011 December 1984
Supporting Documentation Re once-through Steam Generators
ML20135H3531984-06-19019 June 1984
Package of Reactor Operator & Senior Reactor Operator License Exam Questions & Answer Keys for Several Facilities, Including Yankee Rowe,Point Beach Units 1 & 2,Fort Calhoun Unit 1 & Calvert Cliffs Units 1 & 2
ML20024B4941983-07-0606 July 1983
Slide Presentation Entitled Control Room Indications.
ML20078B6461983-04-0505 April 1983
Slide Presentation Entitled TMI-1 Once-Through Steam Generator Repair & Return to Svc
ML20083N6661982-10-19019 October 1982
TMI-1 Once-Through Steam Generator Repair Process Update & Return to Svc Overview
ML20082R1511982-09-15015 September 1982
Slide Presentation Entitled, TMI-1 Once-Through Steam Generator Repair Process Description/Qualification
ML20083N6581982-08-0404 August 1982
Informal Technical Communication Re 820721 Meeting in Livingston,Nj Concerning Schedule for Qualification Program of Tube Repair & Results of Preliminary Tests.Ornl 820817 Memo Re 820808-09 Meeting & Summary of 820915 Meeting Encl
ML20054K0801982-06-10010 June 1982
Request for OMB Review & Supporting Statement Re Psychological Stress of TMI-1 Restart on Residents Living in General Vicinity.Estimated Respondent Burden Is 853-h
ML20071J0471982-04-0707 April 1982
Slide Presentation Entitledd Gpu Nuclear TMI-1 Once-Through Steam Generator Status Review
1998-08-28
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20154H9871998-08-28028 August 1998
Non-proprietary,rev 0 to Calculation of TMI-1 ESF Component Leakage Iodine Release
ML20154P8941998-05-13013 May 1998
Non-proprietary Rev 1 to Psat 05653A.04, Formulation of OTSG DF for Radioiodine (as I2) to Be Credited for TMI-1 Mlsb with Ais/Pas
ML20217E1661998-03-18018 March 1998
Rev 0 to C-1101-826-E540-022, Estimate of Xu/Q Values for TMI-1 Control Bldg Vetilation Sys Exhaust
ML20217E1971998-03-17017 March 1998
Rev 0 to C-1101-826-E540-025, X/Q TMI Ventilation Exhaust Opening
ML20217E1171998-03-17017 March 1998
Rev 0 to C-1101-826-E540-020, Atmospheric Transport X/Qs Using ARCON96 Code - CR Habitability
ML20217F9501997-07-24024 July 1997
Rev 1 to Calculation C-1101-770-E420-018, Derating of Cable Ampacity Due to Raceway Fire Barriers
ML20148T7361996-11-0808 November 1996
Rev 0 to Calculation 6612-96-030, Rms Levels Corresponding to NUMARC Eals
ML20148T7511996-11-0606 November 1996
Rev 0 to Calculation 6612-96-031, Estimate of RM-G-6 & 7 Reading W/Decreased Vessel Level
ML20129E9941996-10-10010 October 1996
Rev 0 to Calculation C-1101-770-E420-018, TSI Derating of Cable Ampacity
ML20148T6971996-09-11011 September 1996
Rev 0 to Calculation 6612-96-023, Estimated RM-G-22/23 Readings W/Loca at TS Rcs
ML20148T6801996-09-0606 September 1996
Rev 0 to Calculation 6612-96-022, Estimate of RM-G-9 Reading W/Decreased SFP Level
ML20148F0251994-02-0808 February 1994
Rev 0 to Condensate Storage Tank B
ML20148F0081994-02-0808 February 1994
Rev 0 to Condensate Storage Tank a
ML20148F0321993-12-0808 December 1993
Rev 0 to Bwst
ML20148F1331993-09-30030 September 1993
Rev 0 to Make-Up Tank
ML20148F1601993-09-27027 September 1993
Rev 0 to Rc Drain Tank, & Response to Question 23 Sews for Raceways
ML20148F0541993-09-17017 September 1993
Rev 0 to SQ-TI-EG-T-0001A-2, EDG 1A Air Start 2 Reservior Tank 1A
ML20057B9641993-09-10010 September 1993
AX114 & AX115 Ci Loading
ML20148F1451993-09-0101 September 1993
Rev 0 to Nuc Serv Closed Cooling Water Surge Tank
ML20148F1071993-08-31031 August 1993
Rev 0 to Intermediate Colsed Cooling Surge Tank
ML20148F1221993-08-31031 August 1993
Rev 0 to Intermediate Closed Cooling Chem Mix Tank
ML20148F1521993-08-31031 August 1993
Rev 0 to Nuc Svc Cool Chem Mix Tank
ML20057B9581993-08-27027 August 1993
FH109/FH300 Ci Estimate
ML20196K6431991-07-20020 July 1991
Rev 1 to B&W Document 32-1203121-01, Fsplit Certification Analysis
ML20136B1461979-04-0303 April 1979
Calculations Made for Hydrogen Bubble in Reactor Vessel
ML20136A9851979-03-30030 March 1979
Hydrogen Burn Vessel Explosion Possibility Calculations
ML20136B1421979-03-30030 March 1979
Calculations Re Containment Hydrogen Bubble
ML20125D8981978-08-31031 August 1978
Calculation Data Re Davis-Besse 1 Pressurizer Levels During Reactor Trips
ML20076J8441977-08-14014 August 1977
Graph of Reactivity Worths at 532 F & 2155 Psig
1998-08-28
[Table view] |
Text
_ _ .
j . .
l * ;
)5 15,97 08:20:46 i
f
! GPU NUCLEAR B/A No. 128108 W/O No. 95-552A-52108 lI d
I 1
I i SEISMIC QUALIFICATION l
j No. SQ - T1 - E C3-T ~_ooo;A ~1- j
-I l REVISION O i
COMPONENT:
)
j SUBCOMPONENT(B):
l i
1 Sheet 1 of fi Q $ Appen nest At o5 e
I:
i
) !!
- EVALUATED BY:
- DATE EVALUATED BY: DATE f-/7"f 3 i; a
9706040087 970528 PDR ADOCK 05000289 P PDR 77
as-is 97 68:ao:4s At oF M i
Nuclear DOCUMENTNO.
sg _m 7 omr.2 I e0G 1 A M. STMr 2. AEraout.Tw- 1 A REV SUMWHY OF CHANGE APPROVAL DATE I
o T/l7/*)7 caemweetqw ow
! ora c w A.t sQ- M c K A Gs '
l 7/N/W RGv'56b 5,9,- PAcicA GG re gg, 7,g-um.ELT WW D1GSGL G6 Mc4A%R- g g,g, ,
Res Pouse EPGCTA.A (SEE EQG ~~
! 6 ,
[
3,s, w1Jc .trllz 15 i
c A t.c
- 4 7.t o s - c.- o 0 4 , WIG 2.) j io c co e m a , c u = >> .
g, d.yn l
1 i
F 0
O O
4 4
e N0036 (03-90)
'. 1 f Ac
~
) S e 15.- S 7 08:20:46 iSQUGI)ATAiFilEINDEX COMPONENT TAG NUMBER M ~ F ##0dAE--
3ESCntPTtON EDG 1A 4 i Ae .s,v4n-r- 2 AEsex voix
> DOOUMENTS NUMBERS / STATUS SEWS I v
GMS 2 (TECHNICAL FUNCTONS DATA SURVEY)
/
PHYSICAL DRAWING /ASSEWLY DRAWING ( t~~ 8oZ 7 K (A 2'(# ) -
VENDOR CATALOG / DATA /lNSTRUCTION MANUAL INSTALLATCN SPECIFICATCN -
SEtSMIC ANALYSIS / TEST REPORTS /CALCS -
CONCRETE OR PAD DRAWINGS, SPECS, BLDCK walls- -
EMBEDDED STEEL DRAWINGS -
~
ANCHORAGE DRAWING /DCTAILS/ AIDS - !
FIELD CHANGE DOCS /MNCR'S
~~ ~ ~
OTHER l
RL- 4/22-l9T 8
sigherufw
_ POTENTIAL OLTTUER BASE PLATE PLUG WELDS i OTHERS l I
- DISPOSITION NEED MORE DATA
, KNOWN OUTUE.R, SE!SMIC DATA ACCEPTABLE CONF 1MATION WALKDOWN ONLY ANCHORAGE CALCULATONS: _ DaST _ PERFORM IN FIELD COMMEKTS V64-fCY & #0 0 6"6
- lA9 .O STA// 5 /h416r Hb 7" AS NuoJ.b f4.b Msty N67 AG AfsN fo ri cWe CA A 7*!'At'H60 0 GucA&r C .
READY FOR SOUG WAU(DOWN Seismic capacnyEngineer (SCQ mm ,.,
Use reverse sw kt COMMfA
~. 3 bi +
'a ."
)Sc15,-97 08:20:46 Status V N U SCREENING EVALUATION WORK SHEET (SEWS) Sheet 1 of 2 Equip. ID No. EG-T-0001A-2 Equip. Class 21 - Tanks and Heat Exchangers Equipment Description EDG 1A AIR START 2 RESERVOIR TANK 1A Location: Bldg. DG Floor El. 305 Room, Row / Col "A" DG BLDG NR DIESEL Manufacturer, Model, E'tc. (optional)
MORA/Jcd 64o5 t.J -
9 SHELL CAPACITY VS DEMAND Buckling capacity of shell of large, flat-bottom, vertical tank is equal to or greater than demand: Y N U@
I ANCHOR BOLTS AND EMBEDMENT Capacity of anchor bolts and their embedments is equal N7# h to or greater than demand: hU N/A cm W / !
t '
CONNECTION BETWEEN ANCHOR BOLTS AND SHELL !
Capacity of connections between the anchor bolts and I:
the tank shell is equal to or greater than the demand: hN U N/A :
FLEXIBILITY OF ATTACHED PIPING f Attached piping has adequate flexibility to accommodate motion of large, flat-bottom, vertical tank:
rh N U N/A ca+ 2 i
TANK FOUNDATION Ring-type foundation is not used to support large, flat-bottom, vertical tank:
Y N U@ -
ge , .9-IS E0VIPMENT SEISMICALLY ADE0VATf2
[h I
- -- - _ _ ~ . - - - - - - -.. . . _ - - _ . _ . - . _ _ . -
~< .
- ** Y 35-15-97 08:20:46 SCREENING EVALUATION WORK SHEET (SEBS) Sheet 2 of 2 i
- Equip. ID No. EG-T-0001A-2 Equip. Class 21 - Tanks and Heat Exchangers Equipment Description EDG 1A AIR START 2 RESERVOIR TANK 1A COMMENTS I. TA4 SAMi&O on m sk.iar is i4 escio ,4.ue~aw - - ~ .;. s .;.
- u -. :=
, :==mm mr u r n. ,,;;- ;,. _ ,_ ;z w __, ,, L,.
i *
. :;;a rn :semwy m_ . - - _,, peg - ne
'-=
-e, .
$ct: cas m p p_a ,ef ,_ ,_g,7W, ;ggr gCy (4t L 42,O ,
7rw- gusrngar vunm.u,,a_ % .* oc
- osa.f g p 7.sv.qt-Sy i,hltS
- 2. . TRut u Aer rar tumne $ snx o rirx n xxco ro es * * " nase ~ rr l TD 4&mtr rnnu uoss.:rt
). At t, fp A flovD J & Gef sTJI 75LftM f.GQb ~
fiftgb /TJar a %' tes n.c /c Evaluated by: $* Date: /7d'J D W f 17-93
~
. '. AM'"" A 35e16.-97 '08:20:46 Revision 2 Corrected, 6/28/91 Sheet I of 2 Exhibit 5-1 OUTLIER SEISMIC VERIFICATION SHEET (OSYS)
'~
. 1. OUTLIER IDENTIFICATION, DESCRIPTION, AND LOCATION Equipment ID Number S-T-w-t Equipment Class '2/
Equipment' Location: Building M Floor Elevation IOI Room or Row / Column _ ~ Base Elevation Di Equipment Description 50G & A/t N E m /A W
- 2. OUTLIER ISSUE DEFINITION --
- a. Identify all the screening guidelines which are not met.
(Check more than one if several guidclines could not be satisfied.)
Mechanical and .
Electrical Eauipment Tanks and Heat Exchancers Capacity vs. Demand Shell Buckling' -
Caveats Anchor Bolts and Embedment ;
Anchorage v Anchorage Connections Seismic Interaction Flexibility of Attached Piping!
Other Other 1
Cable and Conduit Raceways Essential Relays Inclusion Rules Capacity vs. Demand Other Seismic Performance Concerns Mounting, Type, Limited Analytical Review Location Othef ' . 1 Other l 1 Shell buckling and flexibility of attached piping only apply to large, flat-bottom, vertical tanks.
- b. Describe all the reasons for the outlier (i.e., if all the listed outlier issues were resolved, then the signatories would consider. "(
this item of equipment to be verified for seismic adequacy): l
~
TANK fik) /HWf*ttre>T Ff AChMi GW4 ac. JLA%c fonG CoutA.cG Fouwn%u />p g star tavyggpst ump rtsog,,
S-10
, '., 47 Tact /43*E A 35-15'-97'08:20:46 .
- Revision 2 '
i Corrected,6/28/91 Sheet 2 of 2 i
] Exhibit 5-1 (Cont'd)
OUTLIER SEISMIC VERIFICATION SHEET (OSVS) ,
~
Equipment ID Number fd-7-o00/4
- 3. PROPOSED METHOD OF OUTLIER RESOLUTION (OPTI0fML) j l a. Define proposed method (s) for resolving outlier.
- t. P/-ovice Wa2. urn kr Hweasm. su naowo rnua j
.i
- b. Provide inform'ation needed to implement proposed method (s) for '
resolving outlier (e.g., estimate' of fundamental frequency).
Nh;l OMw rcGdMd Pw (4kksd S 4C-
. C. so T- \ - EGr -r -600 i A - l C,dMd \Milb6 s-o 2 ,,
- 4. CERTIFICATION:
j The information on this OSYS is, to the best of our knowledge and belief, i correct and accurate, and resolution of the outlier issues listed on the
! previous page will satisfy the requirements for this item of equipment to be verified for seismic adequacy:
i Approved by: (For Equipment Classes #0 - #22, all the Seismic j Capability Engineers on the Seismic Review Team (SRT) should sign; i there should be at least two on the SRT. One signatory should be a .
licensed professional engineer. For Relays, the Lead Relay Reviewer should sign.)
"L)k SV07E'u) $S
- Ns%.yYs' Print or Type Name Signature Date
^
%ku M. lor (A 9,W m N. iz-ht/ts Print o'r Type Name SignatbreO ,
Date
)
Print or Type Name Signature . Date J
5-11 I
